• 제목/요약/키워드: circumferential through-wall crack

검색결과 48건 처리시간 0.028초

정확한 비선형 파괴역학 해석을 위한 Ramberg-Osgood 상수 결정법 (On Relevant Ramberg-Osgood Fit to Engineering Non-Linear Fracture Mechanics Analysis)

  • 허남수;김윤재;최영환;양준석;김영진
    • 대한기계학회논문집A
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    • 제27권9호
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    • pp.1571-1578
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    • 2003
  • This paper proposes a robust method for the Ramberg-Osgood(R-O)fit to accurately estimate elastic-plastic J from engineering fracture mechanics analysis based on deformation plasticity. The proposal is based on engineering stress-strain data to determine the R-O parameters, instead of true stress-strain data. Moreover, for practical applications, the method is given not only for the case when full stress-strain data are available but also for the case when only yield and tensile strengths are available. Reliability of the proposed method for the R-O fit is validated against detailed 3-D Finite Element (FE) analyses for circumferential through-wall cracked pipes under global bending using five different materials, three stainless steels and two ferritic steels. Taking the FE J results based on incremental plasticity using actual stress-strain data as reference, the FE J results based on deformation plasticity using various R-O fits are compared with reference J values. Comparisons show that the proposed R-O fit provides more accurate J values for all cases, compared to existing methods for the R-O fit. Advantages of the proposed R-O fit in practical applications are discussed, together with its accuracy.

관통균열이 존재하는 증기발생기 전열관의 파열압력 평가 (Burst Pressure Evaluation for Through-Wall Cracked Tubes in the Steam Generator)

  • 김현수;김종성;진태은;김홍덕;정한섭
    • 대한기계학회논문집A
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    • 제28권7호
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    • pp.1006-1013
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    • 2004
  • Operating experience of steam generators shows that the tubes are degraded by stress corrosion cracking, fretting wear and so on. These defected tubes could stay in service if it is proved that the tubes have sufficient structural margin to preclude the risk of tube bursting. This paper provides detailed plastic limit pressure solutions for through-wall cracks in the steam generator tubes. These are developed based on three dimensional(3D) finite element analyses assuming elastic-perfectly plastic material behavior. Both axial and circumferential through-wall cracks in free span and in u-bend regions are considered. The resulting limit pressure solutions are given in a polynomial form, and thus can be simply used in practical integrity assessment of the steam generator tubes.

원자력 배관의 공학적 파단전누설 해석을 위한 균열열림변위 계산 (Crack Opening Displacement Estimation for Engineering Leak-Before-Break Analyses of Pressurized Nuclear Piping)

  • 허남수;김윤재;장윤석;양준석;최재붕
    • 대한기계학회논문집A
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    • 제28권10호
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    • pp.1612-1620
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    • 2004
  • This study presents methods to estimate elastic-plastic crack opening displacement (COD) fur circumferential through-wall cracked pipes for the Leak-Before-Break (LBB) analysis of pressurized piping. Proposed methods are based not only on the GE/EPRI approach but also on the reference stress approach. For each approach, two different estimation schemes are given, one for the case when full stress-strain data are available and the other fur the case when only yield and ultimate tensile strengths are available. For the GE/EPRI approach a robust way of determining the Ramberg-Osgood (R-O) parameters is proposed, not only fur the case when detailed information on full stress-strain data is available but also for the case when only yield and ultimate tensile strengths are available. The COD estimates according to the GE/EPRI approach, using the R-O parameters determined from the proposed R-O fitting procedures, generally compare well with the published pipe test data. For the reference stress approach, the COD estimates according to the method based on both full stress-strain data and limited tensile properties are in good agreement with pipe test data. In conclusion, experimental validation given in the present study provides sufficient confidence in the use of the proposed method to practical LBB analyses even though when information on material's tensile properties is limited.

원주방향 관통균열이 용접부 중앙에 존재하는 V-그루브 맞대기 용접배관의 한계하중 해석 (Mismatch Limit Load Analyses for V-groove Welded Pipe with Through-wall Circumferential Defect in Centre of Weld)

  • 김상현;한재준;정진택;김윤재
    • 대한기계학회논문집A
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    • 제37권11호
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    • pp.1379-1386
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    • 2013
  • 본 논문에서는 용접부 중앙에 원주방향 관통균열이 있는 V-그루브 맞대기 용접 배관의 한계하중 해석을 수행하였다. V-그루브 맞대기 용접 배관이 그루브 각 $45^{\circ}$, $90^{\circ}$를 갖는 형상에 대한 한계하중 식을 제시하기 위해 용접 형상의 변화에 따른 용접부 너비를 정의하였고 강도불일치 비, 용접부 너비, 균열 길이 및 배관 반경 비에 대한 체계적인 변수 해석을 수행 하였다. 모재와 용접재는 탄성 완전소성재료로 가정하였으며 상불일치와 하불일치 조건에서의 인장 하중과 굽힘 하중에 대한 강도불일치 한계하중이 강도불일치 비($M_F$)와 형상변수(${\psi}$)를 통해 정량화 됨을 유한요소 해석을 통해 확인하였다.

원자력 배관의 파단전누설 해석을 위한 개선된 참조응력법의 수치해석적 검증 (Application of enhanced Reference Stress Method to Nuclear Piping LBB Analysis : Finite Element Validation)

  • 허남수;김윤재;김영진
    • 대한기계학회논문집A
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    • 제25권4호
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    • pp.741-747
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    • 2001
  • Three-dimensional, elastic-plastic finite element analyses for circumferential through-wall cracked pipes are performed using actual tensile data of stainless steels, for two purposes. The first one is to validate the recently-proposed enhanced reference stress (ERS) method to estimate the J-integral and COD for circumferential through-wall cracked pipes. The second one is to compare those results with the GE/EPRI estimations. It is found that the J-integral and COD estimations according to the GE/EPRI method can be very sensitive to how the stress-strain data are fitted using the Ramberg-Osgood relation. Moreover, no tendency can be found regarding the most appropriate fitting range for the Ramberg-Osgood fit. On the contrary, the J-integral and COD estimations based on the ERS method give more accurate results than the GE/EPRI estimation. The present results provide confidence in applying the proposed method to the Leak-Before-Break(LBB) analysis.

유한요소 해석모델이 원자력 배관의 건전성 평가에 미치는 영향 (Effect of Finite Element Model on the Integrity Evaluation of Nuclear Piping)

  • 허남수;김영진;표창률;유영준
    • 한국안전학회지
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    • 제15권2호
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    • pp.51-58
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    • 2000
  • Recently, the J/T analysis based on elastic-plastic finite element analysis is popularly used in the nuclear industry to assess the integrity of a cracked pipe. The objective of this paper is to evaluate the effect of stress-strain curve for weld metal, variation of crack incremental length(${\delta}a$), and crack face pressure on the J/T analysis result. For this purpose, a parametric analysis was performed and the results calculated from finite element analysis were compared with those from the piping experimental data(stainless steel weldment pipe with circumferential through-wall crack). The numerical result using base metal material property is in agreement with the experimental one and the maximum load is decreased as the ${\delta}a$ for J/T analysis is increased.

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원주방향 균열 존재 증기발생기 전열관에 미치는 지지판의 굽힘제한 영향 (Restrained Bending Effect by the Support Plate on the Steam Generator Tube with Circumferential Cracks)

  • 김현수;진태은;김홍덕;정한섭;장윤석;김영진
    • 대한기계학회논문집A
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    • 제31권2호
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    • pp.277-284
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    • 2007
  • The steam generator in a nuclear power plant is a large heat exchanger that uses heat from a reactor to generate steam to drive the turbine generator. Rupture of a steam generator tube can result in release of fission products to environment outside. Therefore, an accurate integrity assessment of the steam generator tubes with cracks is of great importance for maintaining the safety of a nuclear power plant. The steam generator tubes are supported at regular intervals by support plates and rotations of the tubes are restrained. Although it has been reported that the limit load for a circumferential crack is significantly affected by boundary condition of the tube, existing limit load solutions do not consider the restraining effect of support plate correctly. In addition, there are no limit load solutions for circumferential cracks in U-bend region with the effect of the support plate. This paper provides detailed limit load solutions for circumferential cracks in top of tube sheet and the U-bend regions of the steam generator tube with the actual boundary conditions to simulate the restraining effect of the support plate. Such solutions are developed based on three dimensional finite element analyses. The resulting limit load solutions are given in a polynomial form, and thus can be simply used in practical integrity assessment of the steam generator tubes.

Structural Integrity Evaluation of Steam Generator Tube with Two Parallel Axial Through-Wall Cracks

  • Moon Seong In;Kim Young Jin;Lee Jin Ho;Song Myung Ho;Park Youn Won
    • Nuclear Engineering and Technology
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    • 제36권4호
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    • pp.327-337
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    • 2004
  • It is commonly required that tubes with defects exceeding $40\%$ of wall thickness in depth should be plugged; however, this criterion is too conservative for some locations and for some types of defects. Many studies have been done with the aim of developing an alternative plugging criteria, and these studies have shown that steam generator tubes with a certain range of axial through-wall cracks could remain in service without any safety or reliability problems. However, these studies have been limited, thus far, to consideration of single cracked tubes, necessitating a study on multiple cracks, which are commonly found. A crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed in the previous study. In this paper, the investigation is extended to the parallel axial cracks spaced in a circumferential direction, because parallel axial cracks are more frequently detected during in-service inspections than collinear axial cracks. Interaction effects between two parallel cracks are evaluated by performing elastic and elastic-plastic finite element analyses.

관통균열 세관의 파열압력 예측을 위한 탄소성 파괴역학 해석 (Elastic-plastic Fracture Mechanics Analyses for Burst Pressure Prediction of Through-wall Cracked Tubes)

  • 장윤석;문성인;김영진;황성식;김정수;김윤재
    • 대한기계학회논문집A
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    • 제29권10호
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    • pp.1361-1368
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    • 2005
  • The structural and leakage integrity of steam generator tubes should be sustained all postulated loads with appropriate margin even if a crack is present. During the past three decades, for effective integrity evaluation, several limit load solutions have been used world-widely. However, to predict accurately load carrying capacities of specific components under different conditions, the solutions have to be modified by using lots of experimental data. The purpose of this paper is to propose a new burst pressure estimation scheme based on fracture mechanics analyses for steam generator tube with an axial or circumferential through-wall crack. A series of three dimensional elastic-plastic finite element analyses were carried out and, then, closed-form estimation equations with respect to both J-integral and crack opening displacement were derived through reference stress method. The developed engineering equations were utilized for structural integrity evaluation and the resulting data were compared to the corresponding ones fiom experiments as well as limit load solutions. Thereafter, since the effectiveness was proven by promising results, it is believed that the proposed estimation scheme can be used as an efficient tool for integrity evaluation of cracked steam generator tubes.

소변형 이론에 입각한 감육이 존재하는 90 도 곡관의 소성 한계 하중 (II)- 굽힘 - (Plastic Limit Loads of 90° Elbows with Local Wall-Thinning Using Small Strain FE Limit Analyses (II)- Bending Moment -)

  • 김종현;안중혁;홍석표;박치용;김윤재
    • 대한기계학회논문집A
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    • 제31권4호
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    • pp.496-505
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    • 2007
  • This paper proposes closed-form plastic limit load solutions for elbows under in-plane bending, via three-dimensional (3-D), small strain FE limit analyses using elastic-perfectly plastic materials. A wide range of elbow and thinning geometries are considered. For systematic analyses of the effect of the axial thinning length on limit loads, two limiting cases are considered; a sufficiently long wall thinning, and the circumferential part-through surface crack. Closed-form plastic limit load solutions for wall thinning with intermediate longitudinal extents are then obtained from these two limiting cases. The effect of the axial extent of wall thinning on plastic limit loads for elbows is highlighted by comparing that for straight pipes. Although the proposed solutions are developed for the case when wall thinning exists in the center of elbows, it is also shown that they can be applied to the case when wall thinning exists anywhere within the elbow.